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Preservation of Documents by Lamination

Description: From Abstract: "Composition and performance specifications for a cellulose acetate laminating film suitable for a cellulose acetate laminating film suitable for archival use are presented. The properties of polyethylene and polyethylene terephthalate films of interest in connection with their possible use for the protection of documents are discussed."
Date: October 30, 1959
Creator: Wilson, William K. & Forshee, B. W.
Partner: UNT Libraries Government Documents Department
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Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant

Description: From abstract: "Neutronic characteristics, the control and instrumentation system, equipment description and plant safety considerations of the ML-1 (mobile, low power) nuclear power plant. The site is described with reference to geology, climate, and population density."
Date: September 30, 1959
Creator: Linenberger, G. A.
Partner: UNT Libraries Government Documents Department
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SRE Fuel Element Damage: An Interim Report

Description: Abstract: During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high. Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated.
Date: November 30, 1959
Creator: Jarrett, A. A.
Partner: UNT Libraries Government Documents Department
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REPORT OF FIRE IN LABORATORY HOOD, WING I, BUILDING 4500, MAY 22, 1959

Description: Approximately 16 to 18 liters of isopropyl alcohol in a 20-liter glass carboy in a floor type hood were ignited by infrared heat lamps used to heat the carboy and contents. A technician received several minor lacerations on the hand. (C.H.)
Date: July 30, 1959
Creator: Hungerford, T W & Lain, J E
Partner: UNT Libraries Government Documents Department
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MODEL STUDIES OF FLOW AND MIXING IN THE PARTIALLY ENRICHED GAS-COOLED POWER REACTOR

Description: A quarter-scale flow model, using air as a working fluid, was used to obtain design data for the PEGCPR program. A design for the core-support cylinder, to provide optimum mixing and core-flow distribution, was developed, following which experimentul studies of core-flow distribution, mixing of flow from the two inlets, flow patterns in plenum spaces, flow patterns in the thermal- shield-coolant passage, and pressure drops throughout the model were carried out. Results obtained in the model wer… more
Date: November 30, 1959
Creator: Flanigan, L.J.; Whitacre, G.R. & Hazard, H.R.
Partner: UNT Libraries Government Documents Department
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Electrophoretic Processes--Nuclear Aspects. Final Report for December 1, 1956-June 30, 1959. Vitro Job 2091

Description: The feasibility of the electrophoretic (electrokinetic) coating process has been demonstrated for a number of nuclear applications. The major portion of the experimental program was directed toward work which leads to: development of electrophoretic coatings which should be useful for the protection of graphite and graphite fuel elements against physical and chemical attack under reactor conditions. Several of these coatings also show promise for fission product retention; a technique for apply… more
Date: September 30, 1959
Creator: Keeler, R. A. & Klach, S. J.
Partner: UNT Libraries Government Documents Department
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AIR CORE CRYOGENIC MAGNET COILS FOR FUSION RESEARCH AND HIGH ENERGY NUCLEAR PHYSICIS APPLICATIONS

Description: It is shown that cryogenic techniques offer the possibility of substantially improving the efficiency and practicality of generating high magnetic fields in air-core coils of large size. Over-all reductions in power requirements of as high as 25, by comparison with conventional coils, are predicted, provided high purity conductors and efficient refrigeration cycles are used. (W.D.M.)
Date: October 30, 1959
Creator: Post, R. F. & Taylor, C. E.
Partner: UNT Libraries Government Documents Department
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FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. PHASE I. Progress Report for May 1, 1959 to October 31, 1959

Description: Numerous types of high temperature ceramic fuel elements for the Pebble Bed Reactor are being evaluated. Specimens are 1 1/2 in. diameter uranium graphite spheres with external coatings such as silicon carbide or pyrolytically deposited high density graphite and fuel particle coatings such as alumina. Low fission product leakage rates at high temperatures have been observed for some of these coatings. High-level irradiation has given no visible evidence of radiation damage to either the silicon… more
Date: November 30, 1959
Partner: UNT Libraries Government Documents Department
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Variable Moderator Reactor Development Program. Quarterly Progress Report No. 2

Description: The hydrodynamics code BOCH was used to obtain the relationship between a large number of variables such as voids, flux, pin spacing, power density, and pressure for VMR lattices. Based upon these relationships, a reference core design was selected for examination, using the integrated physics and hydrodynamics analytical modeis. The analog representations of the VMR core kinetics describing the individual blocks of a model block diagram were completed. A simplified core physics analysis was co… more
Date: November 30, 1959
Partner: UNT Libraries Government Documents Department
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Preliminary Studies of Scavenging Systems Related to Radioactive Fallout. Summary Report

Description: Preliminary studies were made of the relationship between the size of particles suspended in the lower atmosphere and the amount and nature of radionuclides they contain. Emphasis was placed on the distribution of strontium90. From a limited number of analyses, it was found that strontium-90 is associated primarily with particles below 0.1 micron in diameter. Preliminary studies were made of scavenging of particles by liquid water droplets. Studies are included of sticking probability and the e… more
Date: April 30, 1959
Creator: Rosinski, J. & Stockham, J.
Partner: UNT Libraries Government Documents Department
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RBU: A COMBINED MONTE CARLO REACTOR-BURNUP PROGRAM FOR THE IBM 709

Description: RBU is a digital computer program for the detailed calculation of the neutron, reactivity, and isotopic history of a reactor in which relatively exact models of the geometry and physical processes are included to permit reliable pre dictions of fuel costs and reactor performance. The program uses the Monte Carlo method to obtain the fine structure of the neutron flux in three space dimensions and energy. Using this fine structure, cross sections are averaged over space and energy to obtain the … more
Date: September 30, 1959
Creator: Leshan, E. J.; Burr, J. R.; Temme, M.; Thompson, G. T. & Triplett, J. R.
Partner: UNT Libraries Government Documents Department
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Summary Report, 1954-1959 Raw Materials Development Laboratory Winchester, Massachusetts and Grand Junction, Colorado

Description: A brief review of the research work performed by the National Lead Company on the recovery of U from its ores is presented. A bibliography is presented which includes all reports on raw materials published by National Lead Company through Dec. 1958. Also included is a list of complete publications on raw materials from 1944 to 1954. (W.L.H.) low conditions at room temperature. Emphasis was placed on the effect of reaction parameters and mercury-recovery techniques on the Hg/sup 202/ content of … more
Date: September 30, 1959
Creator: Beverly, R.G. ed.
Partner: UNT Libraries Government Documents Department
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SN-1 Research and Development Program Interim Report No. 2 on Core Measurements. Task No. VII

Description: Physics experiments were performed on the SM-1 core. Measurements were made on five rod bank positions and rod calibrations. The reactivity effects of core modifications were investigated. Modifications to the core included replacement of the boron absorbers in rods 1, 2, 3, 4 and C with europium absorbers; replacement of a control rod fuel element with one containing an integral europium flux suppressor; and replacement of a stationary fuel element. Additional experiments were designed to dete… more
Date: June 30, 1959
Creator: MacKay, S. D. & Tubbs, D. C.
Partner: UNT Libraries Government Documents Department
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SRE FUEL ELEMENT DAMAGE. Interim Report

Description: During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated. A series of fuel element inspections was begun to ascertain the cause of these circumstances, and several fuel elements were discovered to have suffered substantial damage. O… more
Date: November 30, 1959
Creator: Jarett, A.A. ed.
Partner: UNT Libraries Government Documents Department
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The Thermal Expansion of Synthetic Graphites at Temperature Intervals Between 80 and 2000f

Description: The mean linear and cubical coefficients of thermal expansion of eight commercial samples of graphite were determined for temperature intervals between 80 and 2000 deg F. The linear thermal expansion was measured with an automatic recording dilatometer using a rod-shaped specimen 2 in. long and 1/4 in. across. The specimen was heated in an atmosphere of helium. The results were in good agreement with those of Currie, Hamister, and MacPherson. The mean linear coefficient was found to increase wi… more
Date: November 30, 1959
Creator: Allen, R. D.
Partner: UNT Libraries Government Documents Department
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AN ESTIMATION OF THE EXPLOSION HAZARD DURING REPROCESSING OF METALLIC URANIUM FUEL ELEMENTS METALLURGICALLY BONDED TO ZIRCALOY CLADDING

Description: BS>Experimental studies were performed to define the behavior in ammonium fluoride solutions of uraniumzirconium alloys and of explosive residues isolated from such alloys. The results indicate that once the diffusion layer existing between the uranium core and the Zircaloy cladrung is exposed to such solutions, it will readily and completely dissolve, thus eliminating the possibility of this portion of the diffusion layer entering into an explosive reaction with nitric acid. Because of the pro… more
Date: September 30, 1959
Creator: Swanson, J.L.
Partner: UNT Libraries Government Documents Department
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The Design of Large Cryogenic Magnet Coils. Paper No. 2

Description: Preliminary design and experimental work aimed toward fabrication of large magnet coils with encapsulated sodium conductors is outlined. Aspects of cooling cycles are discussed along with heat transfer, thermal stability, and the mechanical reinforcement of such coils. (J.R.D.)
Date: October 30, 1959
Creator: Taylor, C. E. & Post, R. F.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report for January 1959

Description: Two alternate systems, acetic acid-nickel and acetic acid-cobalt, were examined for possible replacement of the corrosion system: ferric chloride-nickel which is being used in the current transpiration corrosion protection studies. Two Fluorox fluidized bed runs were made, of 9 and 58 hr duration, in which dry air and oxygen were used as oxidizing and fluidizing gases. Tests of the hydroclone classification of thoria indicated that more than 95% of the +0.5 micron particles can be removed from … more
Date: April 30, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
Partner: UNT Libraries Government Documents Department
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Quarterly Report of the Solution Materials Section for the Period Ending January 31, 1959

Description: Deposition of U, Cu, and Ni sulfates from dilute simulated HR fuel solution circulated through a heated Zircaloy-2 pipe section is reported. It was found that deposition occurred under boiling conditions in horizontal pipes because of a gas space which prevented wetting in the upper part of the pipe. Other salt deposition studies in an in-pile loop are reported. Effectiveness of oftwo different hydroclone mountings in removing corrosion products from a loop was studied. Results of chemical stab… more
Date: January 30, 1959
Creator: Griess, J. C.; Savage, H. C.; Greeley, R. S.; English, J. L.; Bolt, S. E.; Hess, D. N. et al.
Partner: UNT Libraries Government Documents Department
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Hazards and Safety Measures Related to Nuclear-Powered Merchant Ships: An Annotated Bibliography of Declassified Literature

Description: This compilation contains 202 abstracts of reports and documents on subjects related to maritime reactor safety; the abstracts are indexed in thc AEC Abstracts of Classified Reports'' (ACR). These ACR references were listed as unclassified or declassified in TID-4021, TID-40.35, and TID-4035, Supplement 1. The abstracts were selected as a part of the preparation of the classified bibliography (ALI-50, printed August 30, 1958) on this same subject. (See also SO-6200, Septcmber 15, 1957, unclassi… more
Date: March 30, 1959
Creator: White, M. K.
Partner: UNT Libraries Government Documents Department
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Methods for the Study of Gas-Metal Reactions in Ultra-High Vacuum

Description: A critical review of the methods reported in the literature for the study of gas-metal reactions in high and ultra-high vacuum systems is given. Experimental apparatus and techniques based on volumetric, gravimetric, magnetic, and other properties of the metals including work function, accommodation coefficient, resistivity, and others have been used. A volumetric method, based on a determination of rate-of-reaction, was selected as most readily applicable to the proposed investigation. (auth)
Date: June 30, 1959
Creator: Love, G.R.
Partner: UNT Libraries Government Documents Department
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Quarterly Report of the Solution Materials Section for the Period Ending April 30, 1959

Description: Studies concerned with the deposition of salts from simulated fuel solution under boiling conditions were continued. Additional deposition tests were carried out in loop L-2-23 in which the core section was heated. Several reagents were tested to determine their ability to dissolve stainless steel corrosion products. A simulated HRT fuel solution was stable with regard to U concentration when diluted to 23 ppm at 250 C; however, some Cu was lost from solution. Preliminary tests in a uranyl sulf… more
Date: April 30, 1959
Creator: Griess, J. C.; Savage, H. C.; Greeley, R. S.; English, J. L.; Bolt, S. E.; Hess, D. N. et al.
Partner: UNT Libraries Government Documents Department
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CUREBO: A GENERALIZED TWO-SPACE-DIMENSIONAL CODING WITH CROSS-SECTION AND DEPLETION CALCULATIONS FOR THE IBM 704

Description: The CUREBO code for the IBM 704 is described. The code is divided into three parts including the calculation of nuclear cross section of the various physical components of a reactor (WOX7), the solution of the multigroup diffusion equations in two-space dimensions in order to find neutron fluxes and sources for an operating reactor containing these components ( CURE), and the calculation of fuel and poison depletion as a result of operating this reactor under steady- state conditions (BO2). (au… more
Date: April 30, 1959
Creator: Archibald, J.A. Jr.
Partner: UNT Libraries Government Documents Department
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